ML19220B814
| ML19220B814 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/08/1978 |
| From: | Herbein J Metropolitan Edison Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| GQL-0824, GQL-824, NUDOCS 7904270403 | |
| Download: ML19220B814 (8) | |
Text
.
?,
1727A m
,"/.;;:::,,
-,, m.oc.,m METROPOLITAN EDISON COMPANY
..m PCST OFFICE SCX 54:
REACING, PENNsYLVANI A 19603 TELEPwCNE 215 - 9:3-0601 May 3, 1973 M
=~
O
% Os;:c"
,.e.
m t;;
- w. -
- = O Mr. 71:00r Etel10, Direct 0r
~
Division of C;erating Rese: Ors d '. D.
s U. S. :Tuclear Regulatcry Cen=issic:
" h ' ',
3 EFj
~4 ashing On, D.C.
20555 3
"3 n
a m
u Dea-Mr. Stello:
s
References:
(a) Meense.To. CFE.50, Ocche: :TO. 50-269
.3, n.ceke.,To. w-e.,
., cense
.,7.
.,ca i
,en a
(b) letter, 71cter Stel10, Jr.,:iEC to All anua:f 5,
,,a.yr.
ran.,eensee, -
w c
In respense to your request to provide a detailed schedule for our evaluation of as/n=etric LOCA leads (reference (b)) en Sree Mile Island :Tuclear Station
' Units 1 and 2), we have attached a repc : entitled, "3&~4 177 FA Cvner's Group Asyn=etric LCCA Leads Ivaluation Progrs='.
'"he schedule presented is consis-tent vith ycur intentiens to reselve this issue within 've years, ander the analysis assu=;tices described in the attached re;cr..
As can be de**~d ed f = the re;crt, ve plan Oc evaluate the asy_.etric leads issue in three distine; phases, with the executic: Of Phases 2 and 2 teing dependent upon the results of Phase 1.
Only the details Of the Phase i evaluatien have been included in the attached reper..
Shculd ve find it necessa:f to proceed to Phases 2 and 3, ve vill trans '- da-ailed schedules f:r these phases to ycu in advance of executing them.
- 'a -aquested evaluatics as a participant Please note that we ar engag=A cf the 3&W 177 hel Assenbly Cvner's Orcup and whenever justified, plar ::
take advantage of generi analyses.
Sincerely, s
/
/
n s.e_4.
,/
c.
.o u.
2
/
71:e President ~1enerati:n
/
w a:r.w::as
/
gy 83 0C1 Attach =en b
o\\
O
\\
b 7904270403>
m?i:31oo41 0
\\s,
e 3&W 177?A Ci4NERS GROUP AS E s_.
LCCA LOADS EVALUATIONS PROGRAM Arkansas Power & Light - ANO 1 Duke Power Cc=pany - Oqcnee 1,
?.,
3 Florida Power Corporatien - Crystal River 3 Metropolienn Edison Ccapany - Three Mile Island 1, 2 Sacraneato Municipal Utility District - Rancho Seco
i 5.0 A??LICA3LZ 3&*4 TCPICAL REPORTS (continued) a.
3rd-10131 - Reacec: Coolant Syste= Structural Analysis b.
3r4-10127 - LCCA Pipe 3reak Criteria for the Design of 3abccck &
'Jilccx Nuclear Steam Syste=s c.
3r4-10132 - Analytical Methods Description - Reactor Ceclant System E'/ rody-nmic Leadings During a Loss-of-Ccolant Accident d
d.
3r4-10133 - Mark C Fuel Assembly - LCCA - Seismic Analyses e.
Br4-10060 - Reac:cr Internals Design / Analysis for Nor=al, Upset and Faulted Conditicas 6.0 P1XI SCHI"CLES 6.1 Phase 1 schedult. is as follows:
Activity 1978 Description April May June July August Septe=ber Cetober
- 1. Preli=inary Scoping Study (?aragraph e
3.1.1)
- 2. Reactor Internals LCCA Pressure Analysis (paragr.>.ph c
3.1.2)
- 3. Reactor Cavity Asy==etric Pressure e
Analysis (?ar.tgraph 3.1.3)
- 4. Results Assess =ent c
(?aragraph 3.1.I.)
6.2 Phase 2 and 3 schedules cannet be considered fir = until specific detail needs are known. Ecwever, the oveuil,;rrru schedule is as follows:
83 CO3
~
6.2 (continued) 1978 1979 1980 IA A? h!AJU JU AC SE hC MA A? M K JU AC SE pC NO E JA FE p!A AP MA JU pT iU SE OC NO DE JA FI LICE!SD;G 3
a 1'
I
(
l i
i l
PRELDi! NARY EARDWARE i MCDIFICATICN w
4 ASSESSME'iT I
I I
l l
I 3
DETA"E A'3'!"SES s
v 6.3 As shewn in paragraph 6.2, all analysis can probably be ce=pleted within the tso year ti=e frs=e discussed in the NRC letter.
Ecw-ever, if hardware =cdifications are required, full i=plementation would exceed the tso year ti=e fra=e allcwing for =aterial precure-ment, fabrication, scheduled shutdowns and erection.
The NRC will be kept advised of fir = dates aJ they are determined.
Go-s o L 4
3.0 WORK PLAN (?HASIS) (centinued) 3.2 Phase 2 analysis will be initiated if results of Phase 1 indicate a need for note datailed review and/or a need for note detailed review and/or a need to review sene of the plants on a specific case basis.
The extent of analysis cannot be specified until the results of Phase 1 are known.
During this phase, ene, or a cenbination, of the following thr ee action paths will be pursued:
a.
Detailed.3c117ses b.
Eardwara Modifications c.
Licensing Actices As in Phase 1, this phase will focus on the Reacter Vessel and structures /cenponents in close proxinity.
If the results of Phase 1 are acceptable, conclusive and defendable, t.his phase vill not be executed.
If it is required to progress on to this phase, an addi:1ccal detailed plan with schedules vill be subnitted to the C d ssion.
3.3 Whereas Phase 2 concentrates en the Reacter Vessel area, as, 3
will fccus on the Stean Generator and R.C. Pu=p areas, Ph
.nalysis vill be initiated culy if the resu!.cs of Phase 1 indicate a need for a nore detailed review.
Here again, there crists the possibility of three ccurses of action, as curlined in paragraph 3.2, and until the specific needs are identified fres Phase 1 efforts, the details of this phase cannot be identified.
If it is required to execute this phase, an addi-tional detailed plan w1:h schedules will be sub=1::ed to the Cc=nission.
4.0 CCMPL us CCDES In the perf ernance of the analyses, several dif f erent cenputer ccdes will be used.
The folicwing list identifies these ccdes:
a.
ANSYS b.
ADINA c.
ST3DS d.
LUMS e.
STARS f.
C RAFT 2 g.
RELA?4 5.0 A??LICA3LZ 3&W TCPICAL RE?CRTS Techniques described in ::pical reports sub=itted to the NRC by the 35W Cenpany vill be used in the evaluation. These Ocpical reports are:
f
- w u s)
-s
2.0 E7AL"ATION 3ASES (continued) effect on the '
- ans=itted to the backup structures to which the ec=ponent is e ud will be included.
2.6 Where applicable, a generic review of the 3&W Owners Group plants will be used. The categorization tining and extent will be discussed later in this report.
3.0 WORK pian (??lSES) 3.1 ?hase 1 will be a seven =enth preliminary assess =ent.
The specific plant drawings will be reviewed to assess whether asy==etric pressures can be applied to si=1lar plants in each category.
3.1.1 A pre 14-dnary scoping study of each plant's restraint design will be perforned. The results of this study will provide esti=ated =axi=u= pipe break opening areas f or each of four breaks (upper cold leg and hot leg guillotine at the Reactor Vessel no::le and upper cold leg and hot leg guillotine out-side the reactor cavity shield wall).
The location of the break outside the reactor cavity shield wall will be deter =ined with acceptable break location criteria. Design cases will then be selected based on para =etric studies perfor:ed by 3&W on their 2057A plants as co=nt;ec to the 177?A plants.
3.1.2 The peak =agnitudes of the =ajor LCCA load co=ponents acting on the reactor internals will be estimated as a function of break si:e. Sensitivity study results which are available for 36W 205FA plants will be used to develop scaling factors for esti=ating loads on the 1777A plants. The particular loads which will be considered are (1) total lateral force on the core support cylinder; (2) total vertical force on the reactor vessel due to head differential pressure; and (3) vertical force on the core.
These loads will be esti=ated for the fcur breaks described in paragraph 3.1.1.
3.1.3 The =agnitude of the peak lateral force which acts externally en the reactor vessel due to asy==etric pressures within the reactor cavity will be esti=ated.
These esti=ates will be extrapolaticas =ade fro existing 177 cavity pressure data to include a consideration of break si:e.
3.1.4 The applied loadings and the loam carrricg capabill:7 of the Reactor Internals and the Reacecr 7essel support for each plant will be ec= pared using the esti=ated asy==e:ric cavity and internals pressures determined in paragraphs 2.1.3 and 3.1.3.
Based on this co=parison, additiona_ analyses and/or hardware =cdifications will be recoc= ended.
~% W h fL $3 C-t ]
w
1.0 --L'TRCDUCTICN This report su==arizes the detailed plan prepared by the 35*J 177FA Owners Group in response to the NRC Division of Operating Reactors letter deced January 25, 1978.
The plan described herein is separated into three phases.
Each phase is describec to the level of detail possible at this time.
The phasing is intended to allcw progression tcward a ce=pleted assessment by previdirg for intermediate evaluations as the progras preceeds.
This plan is based upon the un erstandings achieved in a =eeting between the 3&*J Owners Group and NRC/ DOR on March 31, 1978.
2.0 EVALCATICN 3ASES 2.1 All ec=ponents listed in Enclosure 4 of Ref erence (b) will be addressed for the LOCA breaks evaluated.
These include:
a.
Reactor Vessel b.
Fuel Asse=blies, Including Grid Structures c.
Control Red Drives d.
ECCS Fiping attached to the Pri=ary Coolant Piping e.
Reactor Coolant Systes Piping f.
Reactor Vessel, Stes= Generater and Punp Supports g.
Reacter Internals h.
Reactor Cavity Shield Wall and Neutron Shield Tank
- i. Stea= Generator Sub-ce=part=ent Wall 2.2 LCCA analyses will be perfor=ed for breaks rendering the worst loadings for the Reactor Vessel supporrs and Reactor Internals. For these breaks, all ec=ponents listed in paragra -h 2.1 will be evaluated to assure (1) =aintenance of a coclable core gec=etry and (2) =1tigation of the consequences of an accident.
2.3 Jet impinge =ent eff ects will be evaluated for breaks analyzed.
This evaluation was not explicitly stated in the NRC letter, but was identified as a requirement in the March 31, 1978, =eeting mentioned in paragraph 1.0.
2.4 As appropriate, the evaluation will censider:
li=ited displace =ent break areas where applicable a.
b.
use of actual time-dependent forcing function c.
reactor support stiffness d.
break cpening ti=es break location utilizing stress criteria e.
2.3 If results of the evaluation indicate leads laading to inelastic action or displace =ents exceeding previous design li=1ts, then inelastic be-havior (including strain hardening) of the naterial analy:ed and the 83 CC7
CCN~ETTS
- 1. 0 Introdue:1on 2.0 Evaluation 3ases 3.0 '4ork Plan (Phases) 4.0 Cc=puter Codes 5.0 Applicable B&*4 Topical Reports 6.0 Schedules 83 CCS